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HL-2A和HL-1M装置采用了激光吹气注入高Z杂质来缓减大破裂中的等离子体电流衰竭,并给出了初步实验结果。在HL-2A装置上建立了利用MHD扰动的参量预报放电破裂先兆的报警系统,研制了MHD实时检测与处理系统,实现了放电破裂先兆的预报、快速触发激光吹气、形成阻性高辐射等离子体、消耗热能和磁能,缓减大破裂。实验证明,这是一种使得大型聚变实验装置在放电破裂之前显著减少等离子体中热能和磁能,而且能安全终止放电的简单、快速和有效的途径。     

用软X射线成像观察HL-2A装置中的杂质注入过程

激光吹气是主动性研究等离子体内部杂质输运的最佳方法之一。杂质的注入用杂质粒子流表示 Г=-DVn＋Lvn 式中，D为输运系数，V为对流速度。激光吹气实验可在放电中选择不同时段注入可控量的杂质。由于杂质注入量很小且附加脉冲信号持续时间很短，等离子体电流和温度都没有明显扰动。杂质约束时间可根据中心道信号衰减时间来计算。     

低混杂波电流驱动下注入杂质的输运

在欧姆放电和低混杂波电流驱动条件下,应用激光吹气技术注入金属杂质,用真空紫外谱仪测量了杂质线的辐射,给出了ＨＬ－１Ｍ 装置欧姆等离子体和低混杂波电流驱动等离子体杂质输运的研究结果。用杂质输运程序ＬＢＯ进行数值模拟,得出了等离子体中杂质的扩散系数Ｄ（ｒ） 和对流速度ｖ（ｒ）。在低混杂波电流驱动条件下,等离子体杂质的输运系数相对欧姆放电等离子体杂质的输运系数减小了５０％ 左右。结果表明,在ＨＬ－１Ｍ 装置上低混杂波电流驱动等离子体相对通常欧姆等离子体杂质的约束性能明显得到了改善     

HL—1M装置等离子体中类锯齿电子密度振荡

在欧姆放电和低杂波电流驱动（ＬＨＣＤ）及激光吹气注入杂质的联合实验中,首次在ＨＬ－１Ｍ 装置上观测到了与软Ｘ射线对应得非常好的锯齿型密度振荡。这种类锯齿型的密度振荡存在于低杂波电流驱动与激光吹气等离子体中。分析表明,该锯齿不是通常的ｑ ＝ １ 有理面上的锯齿,而是在低杂波与杂质共同作用下产生的类锯齿型的密度振荡。一种可能的机制是低杂波电流驱动下杂质的中心积累及崩塌引起的扰动磁场导致了快电子的损失,从而使得密度发生振荡     

HL-lM装置杂质粒子输运与约束特性

在HL-lM装置上利用激光吹气技术,在等离子体边缘瞬态注入少量Al杂质粒子,通过对真空紫外光谱和软X射线区的杂质辐射测量,分别研究了欧姆等离子体和低杂波电流驱动等离子体两种情况下,Al杂质粒子输运与约束特性。结果表明：在欧姆等离子体和低杂波电流驱动等离子体两种情况下,等离子体中心区,在没有MHD锯齿震荡和有MHD锯齿震荡非锯齿破裂期间,杂质粒子输运基本上受新经典规律支配;在有MHD锯齿震荡锯齿破裂期间,杂质粒子输运受MHD不稳定性支配,但其时间很短(通常小于300μs),所以在这种情况下,杂质粒子输运的平均效应比新经典值稍大。而约束区杂质粒子输运则比新经典的值大很多,是反常的。在一定条件下低混杂波电流驱动可以改善等离子体粒子约束。     

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HL-2A装置MHD不稳定性实时预测破裂系统采用了一种简单有效的方法来预测MHD不稳定性导致的等离子体大破裂。利用Mirnov线圈探测MHD信号,根据信号的振幅或频率特点设定计算方法,来预测等离子体破裂先兆,然后用激光吹气注入杂质来缓解等离子体破裂。研究结果表明,该系统能够实时预测破裂先兆,按量注入杂质后,可达到破裂缓解目的。     

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HL-2A装置激光吹气系统采用了全新自动控制的设计方法,实现了杂质注入量、靶片位移以及激光器被触发的时刻的精确自动控制.运行结果表明,该系统能把杂质的注入量控制在适当的水平,既不对等离子体约束产生影响,又便于光谱测量和杂质粒子输运研究.给出了激光吹气系统的设计,以及初步的实验结果.     

HL-2A装置孔栏位形下激光吹气注入杂质的初步实验结果

在聚变堆条件下，等离子体中杂质将严重影响燃料的浓度，并产生大量的功率损失而倍受关注。普遍用于托卡马克等离子体杂质输运研究的方法是瞬态扰动法，主要以主动注入杂质源来研究杂质的扩散和对流过程。短脉冲型的杂质注入一般可采用快过程的压电阀和激光吹气两种方式，而激光吹气方法是一种不容置疑的最好的杂质输运研究方法，因为杂质的注入时间和注入量都可以得到很好的控制，几乎能研究任何状态的等离子体杂质输运过程并对等离子体参数的扰动最小。杂质输运信息可通过探测杂质离子的辐射来得到，这些辐射主要包括由光谱仪测量的线辐射信号和由软X射线成像技术得到的软X射线辐射信号，通过这些测量可带出杂质分布的空间和时间演化的信息，再利用数值模拟计算编码，重建实验数据，从而得到杂质输运的扩散系数D、对流速度V和约束时间等。     

HL—1M装置等离子体离子温度测量

在ＨＬ－１Ｍ托卡马克装置上，利用８通道中性粒子能谱仪测量的等离子体离子温度。在等离子体电流和密变化、激光吹气、弹丸注入，超声分子束注入和低混杂波加热等实验条件下，观测了Ｔｉ的变化。     

HL—1M装置几种杂质谱线的特性

介绍了ＨＬ－１Ｍ装置真空紫外光谱区的杂质辐射观测结果。对器壁硅化后的杂质特性进行了分析，用激光吹气技术研究了杂质输运，分析了低混杂波电流驱动、弹丸注入实验中杂质谱线的变化。     

Disruption Mitigation Using Laser Ablation of High-Z Impurities in HL-1M Tokamak

Major plasma disruptions are considered to be a serious problem for development of tokamak fusion reactors. The preliminary experiment results in HL-1M presented here describe the methods of amelioration of plasma current quench in major disruptions using laser ablation of high-Z impurities, which support the design of next generation large tokomaks like ITER. Using injection of impurity with higher electric charge can produce resistive highly radiating plasma and increase the radiation cooling of plasma to make a safe termination of the disruption. It can be possibly a simple and potential approach to decrease significantly the plasma thermal energy and magnetic energy before a disruption then obtain a safe plasma termination. The magnetic energy can be dissipated by impurity radiation .     

POTENTIAL SAFE TERMINATION BY LASER ABLATION OF HIGH Z IMPURITY IN THE HL-1M TOKAMAK

A preliminary experiment for triggering a plasma current quench by high Z impurities has been performed on the HL-1 M tokamak. Using injection of impurity with the higher charge of the nuclei allows us to increase the radiation cooling. It can be a simple and potential approach for decreasing significantly the plasma thermal energy before a disruption and for safe termination of the plasma.     

Disruption mitigation using laser ablation of high-Z impurities in HL-1M tokamak

A preliminary experiment triggering a plasma current quench by laser ablation of high-Z impurities has been performed in the HL-1M tokamak. The injection of impurities with higher electric charges into tokamak plasmas can increase the radiation cooling of the plasma. Resistive, highly radiating plasma formed prior to the thermal quench can dissipate both the thermal and magnetic energies, which is possibly a simple and potential approach to reducing significantly the plasma thermal energy and magnetic energy before a disruption thereby a safe plasma termination is obtained.     

Mitigation and prediction of disruption on the HL-2A Tokamak

Injection of high-Z impurities into plasma has been proved to be able to reduce the localized thermal load and mechanical forces on the in-vessel components and the vacuum vessel, caused by disruptions in Tokamaks. An advanced prediction and mitigation system of disruption is implemented in HL-2A to safely shut down plasmas by using the laser ablation of high-Z impurities with a perturbation real-time measuring and processing system. The injection is usually triggered by the amplitude and frequency of the MHD perturbation field which is detected with a Mirnov coil and leads to the onset of a mitigated disruption within a few milliseconds. It could be a simple and potential approach to significantly reducing the plasma thermal energy and magnetic energy before a disruption, thereby achieving safe plasma termination. The plasma response to impurity injection, a mechanism for improving plasma thermal and current quench in major disruptions, the design of the disruption prediction warner, and an evaluation of the mitigation success rate are discussed in the present paper.     

Design and Studies of Disruption Prediction System on the HL-2A Tokamak

In the contemporary large tokamak, the disruptive termination of a discharge will reduce the lifetime of the first wall materials because of the intense heat flux at the energy quench and the intense runaway electrons during the current quench, and generate high electromagnetic forces on vacuum vessel components. The system of disruption warner must be established in the HL-2A tokamak. MHD real-time measuring and processing system has been designed and implemented. The system can be predicted the auras of dischage disruption in real-time, the energy quench and the current quench can be avoidanced.     

KTX反场箍缩装置中等离子体小破裂现象研究

在科大反场箍缩磁约束实验装置(KTX)实验中，观测并研究等离子体的显著位移及其带来的小破裂现象。通过分析H_α 谱线、软X 射线辐射以及磁探针数据，发现其主要特征是破裂前等离子体电流重心的缓慢外移，在小破裂后等离子体电流重心在百微秒时间迅速反向移动，重新达到稳定位形。同时，等离子体小破裂伴随着m=1 的边界磁场扰动、稳定壳上显著变化的涡流、以及H_α 谱线和软X 射线辐射的增强。通过对KTX 小破裂实验数据的分析与统计，得出回弹位移与等离子体位移成线性关系。对等离子体电流分布及稳定壳涡流，建立了唯象电路模型，得出了和实验相一致的结论，确定了稳定壳上快速变化的涡流是等离子体小破裂后回复平衡的重要因素。     

Characteristic of Disruption on HL-2A Tokamak

The tokamak disruption is a dramatic event in which the plasma confinement is suddenly destroyed. Detailed experimental studies of disruptions have been made in many machines. During disruption, the plasma current and plasma thermal energy content collapse in an uncontrollable way, thereby applying mechanical forces and heat loads onto the vacuum vessel components. For that reason, the disruptions in a tokamak must be investigated and the physical processes leading to and occurring at the disruption need to be understood.     

On the ion energy distribution of high current arcs in vacuum

With the experiments presented in this paper, applications of a retarding field analyzer (RFA) for the measurement of the ion energy E _i in a vacuum arc plasma are discussed. The examined plasma was produced by a sinusoidal half-wave vacuum arc current. The experiments were concentrated on evaluating the plasma parameters at the last three milliseconds before current zero. In a current range from 300 A_rms to 10 kA_rms, the ion energy distributions and their peak values were evaluated. With the increase of the arc current, a decrease of the ion energy was found. By additional investigations of the angular distribution of the ion energies, a transition from a collision dominated interelectrode plasma to a freely expanding plasma was observed, depending on the arc current     

利用可见轫致辐射计算EAST有效电荷数

利用弦积分的可见轫致辐射计算了先进实验超导托卡马克(EAST)的有效电荷数。对比分析EAST硼化前后的杂质含量,硼化后有效电荷数减小约40%,碳杂质含量减小约50%。统计分析了2009年EAST春季实验的有效放电,显示有效电荷数与碳杂质线辐射量存在很强的线性关系,得到的拟合系数是3.4~5.8,与等离子体电流和低杂波辅助加热功率都有明确的依赖关系。利用近紫外可见波段全谱对主要杂质的含量进行比较后显示,碳是最主要的杂质,大于其它轻杂质含量。同时,还介绍了新建成的多道轫致辐射诊断系统。     

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In experiments of Keda torus experiment (KTX), a reversed field pinch magnetic confinement device, significant plasma displacement and the following minor disruption phenomenon were observed and studied. Its main feature is the slow outward plasma displacement before the minor disruption and rapid moving backward in a hundred microseconds after the minor disruption, reaching a stable configuration again, indicating by the data of the hydrogen-α spectrum, soft X-ray radiation and magnetic probe. At the same time, the minor disruption is accompanied by the disturbance of the m=1 boundary magnetic field, the rapid variation of the eddy currents on the stabilization shell, and the enhancement of the hydrogen-α spectrum and soft X-ray radiation. Based on the analysis and statistics of KTX minor disruption experimental data, the linear relationship between rebound displacement and plasma displacement is obtained. In this paper, a phenomenological circuit model is established for plasma current distribution and stable shell eddy currents, and the conclusion is consistent with the experimental results. It is determined that the rapidly changing eddy current on the stable shell is an important factor for restoring equilibrium after a minor disruption.